Properties of radioactive wastes and waste containers. [Marlex CL-100]
Description
Major tasks in this NRC-sponsored program include: (1) an evaluation of the acceptability of low-level solidified wastes with respect to minimizing radionuclide releases after burial; and (2) an assessment of the influence of pertinent environmental stresses on the performance of high-integrity radwaste container (HIC) materials. The waste form performance task involves studies on small-scale laboratory specimens to predict and extrapolate: (1) leachability for extended time periods; (2) leach behavior of full-size forms; (3) performance of waste forms under realistic leaching conditions; and (4) leachability of solidified reactor wastes. The results show that leach data derived from testing of small-scale specimens … continued below
Physical Description
15 pages
Creation Information
Arora, H.S. & Dayal, R. January 1, 1984.
Context
This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 44 times. More information about this report can be viewed below.
Who
People and organizations associated with either the creation of this report or its content.
Authors
Publisher
-
Brookhaven National Laboratory
Place of Publication: Upton, New York
Provided By
UNT Libraries Government Documents Department
Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.
Contact Us
What
Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.
Description
Major tasks in this NRC-sponsored program include: (1) an evaluation of the acceptability of low-level solidified wastes with respect to minimizing radionuclide releases after burial; and (2) an assessment of the influence of pertinent environmental stresses on the performance of high-integrity radwaste container (HIC) materials. The waste form performance task involves studies on small-scale laboratory specimens to predict and extrapolate: (1) leachability for extended time periods; (2) leach behavior of full-size forms; (3) performance of waste forms under realistic leaching conditions; and (4) leachability of solidified reactor wastes. The results show that leach data derived from testing of small-scale specimens can be extrapolated to estimate leachability of a full-scale specimen and that radionuclide release data derived from testing of simulants can be employed to predict the release behavior of reactor wastes. Leaching under partially saturated conditions exhibits lower releases of radionuclides than those observed under the conventional IAEA-type or ANS 16.1 leach tests. The HIC assessment task includes the characterization of mechanical properties of Marlex CL-100, a candidate radwaste high density polyethylene material. Tensile strength and creep rupture tests have been carried out to determine the influence of specific waste constituents as well as gamma irradiation on material performance. Emphasis in ongoing tests is being placed on studying creep rupture while the specimens are in contact with a variety of chemicals including radiolytic by-products of irradiated resin wastes. 12 references 6 figures, 2 tables.
Physical Description
15 pages
Notes
NTIS, PC A02/MF A01 - GPO.
Subjects
Keywords
- Alkali Metal Isotopes
- Alkaline Earth Isotopes
- Beta Decay Radioisotopes
- Beta-Minus Decay Radioisotopes
- Cesium 137
- Cesium Isotopes
- Containers
- Creep
- Data
- Days Living Radioisotopes
- Dissolution
- Electron Capture Radioisotopes
- Environmental Transport
- Evaluation
- Even-Odd Nuclei
- Experimental Data
- Hours Living Radioisotopes
- Information
- Intermediate Mass Nuclei
- Isomeric Transition Isotopes
- Isotopes
- Leaching
- Low-Level Radioactive Wastes
- Management
- Mass Transfer
- Materials
- Mechanical Properties
- Nuclei
- Numerical Data
- Odd-Even Nuclei
- Organic Compounds
- Organic Polymers
- Performance Testing
- Polyethylenes
- Polymers
- Polyolefins
- Radioactive Materials
- Radioactive Wastes
- Radioisotopes
- Radionuclide Migration
- Separation Processes
- Stresses
- Strontium 85
- Strontium Isotopes
- Tensile Properties
- Testing
- Underground Disposal
- Waste Disposal
- Waste Forms
- Waste Management
- Wastes
- Years Living Radioisotopes 053000* -- Nuclear Fuels-- Environmental Aspects
STI Subject Categories
- 052002 -- Nuclear Fuels-- Waste Disposal & Storage
- 11 Nuclear Fuel Cycle And Fuel Materials
- 12 Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities
- 36 Materials Science
- 360403 -- Materials-- Polymers & Plastics-- Mechanical Properties-- (-1987)
- 520301 -- Environment, Aquatic-- Radioactive Materials Monitoring & Transport-- Water-- (1987)
- 54 Environmental Sciences
Language
Item Type
Identifier
Unique identifying numbers for this report in the Digital Library or other systems.
- Other: TI85000891
- Report No.: BNL-NUREG-35283
- Grant Number: AC02-76CH00016
- Digital Object Identifier: https://doi.org/10.2172/6154422
- Office of Scientific & Technical Information Report Number: 6154422
- Archival Resource Key: ark:/67531/metadc1107484
Collections
This report is part of the following collection of related materials.
Office of Scientific & Technical Information Technical Reports
Reports, articles and other documents harvested from the Office of Scientific and Technical Information.
Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.
Digital Files
When
Dates and time periods associated with this report.
Creation Date
- January 1, 1984
Added to The UNT Digital Library
- Feb. 22, 2018, 7:45 p.m.
Description Last Updated
- July 10, 2019, 11:34 a.m.
Usage Statistics
When was this report last used?
Interact With This Report
Here are some suggestions for what to do next.
Start Reading
Citations, Rights, Re-Use
International Image Interoperability Framework
We support the IIIF Presentation API
Print / Share
Links for Robots
Helpful links in machine-readable formats.
Archival Resource Key (ARK)
- ERC Record: /ark:/67531/metadc1107484/?
- Persistence Statement: /ark:/67531/metadc1107484/??
International Image Interoperability Framework (IIIF)
- IIIF Manifest: /ark:/67531/metadc1107484/manifest/
Metadata Formats
- UNTL Format: /ark:/67531/metadc1107484/metadata.untl.xml
- DC RDF: /ark:/67531/metadc1107484/metadata.dc.rdf
- DC XML: /ark:/67531/metadc1107484/metadata.dc.xml
- OAI_DC: /oai/?verb=GetRecord&metadataPrefix=oai_dc&identifier=info:ark/67531/metadc1107484
- METS: /ark:/67531/metadc1107484/metadata.mets.xml
- OpenSearch Document: /ark:/67531/metadc1107484/opensearch.xml
Images
- Thumbnail: /ark:/67531/metadc1107484/thumbnail/
- Small Image: /ark:/67531/metadc1107484/small/
URLs
- In-text: /ark:/67531/metadc1107484/urls.txt
Stats
- Usage Stats: /stats/stats.json?ark=ark:/67531/metadc1107484
Arora, H.S. & Dayal, R. Properties of radioactive wastes and waste containers. [Marlex CL-100], report, January 1, 1984; Upton, New York. (https://digital.library.unt.edu/ark:/67531/metadc1107484/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.